Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor
In this work, the relative neutron flux was determined experimentally using neutron activation analysis (NAA) method along the length of the dry channel (GUIDE TUBE) of the Isfahan miniature neutron source reactor (MNSR). This reactor was also simulated using the MCNP code, and the neutron flux dist...
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| Format: | Article |
| Language: | fas |
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Nuclear Science and Technology Research Institute
2011-05-01
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| Series: | مجله علوم و فنون هسته‌ای |
| Subjects: | |
| Online Access: | https://jonsat.nstri.ir/article_428_d868fc8dd23699f848ebc8ba54550717.pdf |
| _version_ | 1797835031772659712 |
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| author | A shirani A sohrabi I shahabi |
| author_facet | A shirani A sohrabi I shahabi |
| author_sort | A shirani |
| collection | DOAJ |
| description | In this work, the relative neutron flux was determined experimentally using neutron activation analysis (NAA) method along the length of the dry channel (GUIDE TUBE) of the Isfahan miniature neutron source reactor (MNSR). This reactor was also simulated using the MCNP code, and the neutron flux distribution along the dry channel was calculated and the results were compared with the measured values. The results showed that the neutron flux distribution peak in the dry channel occurs at a point below the nearest point to the center of the reactor core. This is due to presence of the bottom beryllium reflector. In addition, the simulation program was used to determine the neutron energy spectrum in the dry channel and also in the inner and outer irradiation channels of the reactor. Furthermore, the neutron energy spectrum in an inner irradiation channel of the reactor was compared with the previous studies. |
| first_indexed | 2024-04-09T14:48:01Z |
| format | Article |
| id | doaj.art-9e6a80d75cee47ec8bf43d80dc3e3aae |
| institution | Directory Open Access Journal |
| issn | 1735-1871 2676-5861 |
| language | fas |
| last_indexed | 2024-04-09T14:48:01Z |
| publishDate | 2011-05-01 |
| publisher | Nuclear Science and Technology Research Institute |
| record_format | Article |
| series | مجله علوم و فنون هسته‌ای |
| spelling | doaj.art-9e6a80d75cee47ec8bf43d80dc3e3aae2023-05-02T10:46:49ZfasNuclear Science and Technology Research Instituteمجله علوم و فنون هسته‌ای1735-18712676-58612011-05-013214953428Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this ReactorA shirani0A sohrabi1I shahabi2دانشکده فیزیک، دانشگاه صنعتی اصفهان، صندوق پستی: 83111-84156، اصفهان- ایراندانشکده فیزیک، دانشگاه صنعتی اصفهان، صندوق پستی: 83111-84156، اصفهان- ایرانپژوهشکده تحقیقات و توسعه رآکتورها و شتاب‌دهنده‌ها، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی ایران، صندوق پستی: 1589-81465، اصفهان- ایرانIn this work, the relative neutron flux was determined experimentally using neutron activation analysis (NAA) method along the length of the dry channel (GUIDE TUBE) of the Isfahan miniature neutron source reactor (MNSR). This reactor was also simulated using the MCNP code, and the neutron flux distribution along the dry channel was calculated and the results were compared with the measured values. The results showed that the neutron flux distribution peak in the dry channel occurs at a point below the nearest point to the center of the reactor core. This is due to presence of the bottom beryllium reflector. In addition, the simulation program was used to determine the neutron energy spectrum in the dry channel and also in the inner and outer irradiation channels of the reactor. Furthermore, the neutron energy spectrum in an inner irradiation channel of the reactor was compared with the previous studies.https://jonsat.nstri.ir/article_428_d868fc8dd23699f848ebc8ba54550717.pdfmcnp codemnsr reactorneutron activationneutron energy spectrumneutron flux |
| spellingShingle | A shirani A sohrabi I shahabi Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor مجله علوم و فنون هسته‌ای mcnp code mnsr reactor neutron activation neutron energy spectrum neutron flux |
| title | Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor |
| title_full | Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor |
| title_fullStr | Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor |
| title_full_unstemmed | Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor |
| title_short | Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor |
| title_sort | determination of neutron flux distribution along the dry channel of the mnsr reactor and determination of neutron energy spectrum in this reactor |
| topic | mcnp code mnsr reactor neutron activation neutron energy spectrum neutron flux |
| url | https://jonsat.nstri.ir/article_428_d868fc8dd23699f848ebc8ba54550717.pdf |
| work_keys_str_mv | AT ashirani determinationofneutronfluxdistributionalongthedrychannelofthemnsrreactoranddeterminationofneutronenergyspectruminthisreactor AT asohrabi determinationofneutronfluxdistributionalongthedrychannelofthemnsrreactoranddeterminationofneutronenergyspectruminthisreactor AT ishahabi determinationofneutronfluxdistributionalongthedrychannelofthemnsrreactoranddeterminationofneutronenergyspectruminthisreactor |